• 제목/요약/키워드: Molten Salt

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Corrosion of Containment Alloys in Molten Salt Reactors and the Prospect of Online Monitoring

  • Hartmann, Thomas;Paviet, Patricia
    • 방사성폐기물학회지
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    • 제20권1호
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    • pp.43-63
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    • 2022
  • The aim of this review is to communicate some essential knowledge of the underlying mechanism of the corrosion of structural containment alloys during molten salt reactor operation in the context of prospective online monitoring in future MSR installations. The formation of metal halide species and the progression of their concentration in the molten salt do reflect containment corrosion, tracing the depletion of alloying metals at the alloy salt interface will assure safe conditions during reactor operation. Even though the progress of alloying metal halides concentrations in the molten salt do strongly understate actual corrosion rates, their prospective 1st order kinetics followed by near-linearly increase is attributed to homogeneous matrix corrosion. The service life of the structural containment alloy is derived from homogeneous matrix corrosion and near-surface void formation but less so from intergranular cracking (IGC) and pitting corrosion. Online monitoring of corrosion species is of particular interest for molten chloride systems since besides the expected formation of chromium chloride species CrCl2 and CrCl3, other metal chloride species such as FeCl2, FeCl3, MoCl2, MnCl2 and NiCl2 will form, depending on the selected structural alloy. The metal chloride concentrations should follow, after an incubation period of about 10,000 hours, a linear projection with a positive slope and a steady increase of < 1 ppm per day. During the incubation period, metal concentration show 1st order kinetics and increasing linearly with time1/2. Ideally, a linear increase reflects homogeneous matrix corrosion, while a sharp increase in the metal chloride concentration could set a warning flag for potential material failure within the projected service life, e.g. as result of intergranular cracking or pitting corrosion. Continuous monitoring of metal chloride concentrations can therefore provide direct information about the mechanism of the ongoing corrosion scenario and offer valuable information for a timely warning of prospective material failure.

A methodology for the identification of the postulated initiating events of the Molten Salt Fast Reactor

  • Gerardin, Delphine;Uggenti, Anna Chiara;Beils, Stephane;Carpignano, Andrea;Dulla, Sandra;Merle, Elsa;Heuer, Daniel;Laureau, Axel;Allibert, Michel
    • Nuclear Engineering and Technology
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    • 제51권4호
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    • pp.1024-1031
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    • 2019
  • The Molten Salt Fast Reactor (MSFR) with its liquid circulating fuel and its fast neutron spectrum calls for a new safety approach including technological neutral methodologies and analysis tools adapted to early design phases. In the frame of the Horizon2020 program SAMOFAR (Safety Assessment of the Molten Salt Fast Reactor) a safety approach suitable for Molten Salt Reactors is being developed and applied to the MSFR. After a description of the MSFR reference design, this paper focuses on the identification of the Postulated Initiating Events (PIEs), which is a core part of the global assessment methodology. To fulfil this task, the Functional Failure Mode and Effect Analysis (FFMEA) and the Master Logic Diagram (MLD) are selected and employed separately in order to be as exhaustive as possible in the identification of the initiating events of the system. Finally, an extract of the list of PIEs, selected as the most representative events resulting from the implementation of both methods, is presented to illustrate the methodology and some of the outcomes of the methods are compared in order to highlight symbioses and differences between the MLD and the FFMEA.

Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor

  • Won Jun Choi;Jae Hyung Park;Juhyeong Lee;Jihun Im;Yunsik Cho;Yonghee Kim;Sung Joong Kim
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.1002-1012
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    • 2024
  • To remove insoluble fission products, which could possibly cause reactor instability and significantly reduce heat transfer efficiency from primary system of molten salt reactor, a helium bubbling method is employed into a passive molten salt fast reactor. In this regard, two-phase flow behavior of molten salt and helium bubbles was investigated experimentally because the helium bubbles highly affect the circulation performance of working fluid owing to an additional drag force. As the helium flow rate is controlled, the change of key thermal-hydraulic parameters was analyzed through a two-phase experiment. Simultaneously, to assess the applicability of numerical model for the analysis of two-phase flow behavior, the numerical calculation was performed using the OpenFOAM 9.0 code. The accuracy of the numerical analysis code was evaluated by comparing it with the experimental data. Generally, numerical results showed a good agreement with the experiment. However, at the high helium injection rates, the prediction capability for void fraction of helium bubbles was relatively low. This study suggests that the multiphaseEulerFoam solver in OpenFOAM code is effective for predicting the helium bubbling but there exists a room for further improvement by incorporating the appropriate drag flux model and the population balance equation.

Core design study of the Wielenga Innovation Static Salt Reactor (WISSR)

  • T. Wielenga;W.S. Yang;I. Khaleb
    • Nuclear Engineering and Technology
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    • 제56권3호
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    • pp.922-932
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    • 2024
  • This paper presents the design features and preliminary design analysis results of the Wielenga Innovation Static Salt Reactor (WISSR). The WISSR incorporates features that make it both flexible and inherently safe. It is based on innovative technology that controls a nuclear reactor by moving molten salt fuel into or out of the core. The reactor is a low-pressure, fast spectrum transuranic (TRU) burner reactor. Inherent shutdown is achieved by a large negative reactivity feedback of the liquid fuel and by the expansion of fuel out of the core. The core is made of concentric, thin annular fuel chambers containing molten fuel salt. A molten salt coolant passes between the concentric fuel chambers to cool the core. The core has both fixed and variable volume fuel chambers. Pressure, applied by helium gas to fuel reservoirs below the core, pushes fuel out of a reservoir and up into a set of variable volume chambers. A control system monitors the density and temperature of the fuel throughout the core. Using NaCl-(TRU,U)Cl3 fuel and NaCl-KCl-MgCl2 coolant, a road-transportable compact WISSR core design was developed at a power level of 1250 MWt. Preliminary neutronics and thermal-hydraulics analyses demonstrate the technical feasibility of WISSR.

용융염법에 의한 Sr-ferrite의 생성기구 (Formation Mechanism of Sr-Ferrite by Molten Salt Method)

  • 박준홍;신효순;이병교
    • 한국세라믹학회지
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    • 제31권10호
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    • pp.1181-1187
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    • 1994
  • Sr-ferrite powders were synthesized by molten salt method. The process of powder formation was investigated by controlling the size and shape (sphere and acicular) of starting materials. The morphology of resulting ferrite was plate-like regardless of the shape of starting materials, Fe2O3 powders. As a result, the formation of Sr-ferrite in the molten salt was proceeded by solution-precipitation.

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이트리아 안정화 지르코니아 바인더에 의한 열전지 전기화학적 특성 (Electrochemical Properties of Yttria Stabilized Zirconia Binder for Thermal Batteries)

  • 김지연
    • 한국전기전자재료학회논문지
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    • 제30권5호
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    • pp.331-337
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    • 2017
  • Thermal batteries, reserve power source, is activated by melting of molten salt at the temperature range of $350{\sim}550^{\circ}C$. To immobile the molten state electrolyte when the thermal battery is activated, the binder must be added in electrolyte. Usually, molten salts include 30~40 wt% of MgO binder to ensure electrical insulation as well as safety. However, the conventional MgO binder tends to increase ionic conductive resistance and thus the inclusion of the binder increases the total impedance of the battery. This paper mainly focused on the study of yttria stabilized zirconia (YSZ) as an alternative binder for molten salt. The chemical stability between the molten salt and YSZ is measured by XRD and DSC. And the sufficient path for ionic conduction on molten salt could be confirmed by the enhanced wetting behavior and the enlarged pore size of YSZ. The electrochemical properties were analyzed using single cell tests so that it showed the outstanding performance than that using MgO binder.

담지된 금속염 혼합물 촉매의 표면 연구 (Surface Study on the Supported Molten Salt Catalyst)

  • 김종팔;이광현
    • 공업화학
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    • 제20권4호
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    • pp.381-385
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    • 2009
  • 비균일계 촉매의 일반적인 형태는 촉매로서 활성이 있는 금속 혹은 금속 화합물을 표면적이 넓은 다공성 물질인 지지체에 분산 담지시켜서 금속의 표면적을 높이고 이로부터 금속의 분산이 높아지면서 촉매로서의 활성도 높아져 일반적인 반응에 응용되고 있다. 그러나 본 연구에서는 금속염을 이용한 액상 촉매의 제조 및 응용에 초점을 맞추었다. 일반적인 금속염들은 높은 온도에서도 용융되지 않지만 이 금속염 화합물에 다른 금속염 화합물을 함께 섞어 혼합시키면 이 혼합물이 보통의 비균일 촉매 반응온도인 $200^{\circ}C$에서 $400^{\circ}C$의 범위에서 액상으로 존재할 수 있게 된다. 고온에서 액상형태가 되는 용융된 금속염 혼합물(molten salt)을 지지체의 세공 내에 담지시켜 담지된 액상 촉매로서의 가능성을 알아보고 이들의 촉매 제조와 표면 연구에 초점을 맞추었다. 이들 금속염 혼합물은 종류가 매우 다양하여 여러 종류의 금속에 대하여 혼합염을 선택하여 응용할 수 있다. 본 연구에서는 일반적인 촉매로 많이 이용되고 있는 구리를 선정하고 이의 염화물인 염화구리(CuCl)와 함께 혼합되어 용융될 수 있는 금속염 혼합물을 만들기 위해 칼륨 염화물을 선택하여 CuCl-KCl 혼합염을 촉매 제조에 이용하였다. 이 금속염 혼합물을 지지체에 첨가시킨 양은 담지 시킬 알루미나 세공 부피의 약 25%로 하여 용융된 금속염의 표면적이 넓어지도록 하였고 제조 후의 표면은 SEM와 EDS를 이용하여 분석하였다. 금속염 혼합물은 염산 수용액을 이용하여 함침법으로 담지 시켰으며 제조한 직후와 제조한 후 금속염 혼합물을 용융점 이상으로 3 h 동안 열처리 한 후의 표면을 비교하였다. 실험 결과 표면에서의 CuCl-KCl의 조성은 일정하지 않았지만 이 열처리가 표면에서 금속염 혼합물의 형성을 촉진시키고 있음을 알 수 있었다.

MODELING AND OPTIMIZATION Of A FIXED-BED CATALYTIC REACTOR FOR PARTIAL OXIDATION OF PROPYLENE TO ACROLEIN

  • Lee, Ho-Woo;Ha, Kyoung-Su;Rhee, Hyun-Ku
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2000년도 제15차 학술회의논문집
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    • pp.451-451
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    • 2000
  • This study aims for the optimization of process conditions in a fixed-bed catalytic reactor system with a circulating molten salt bath, in which partial oxidation of propylene to acrolein takes place. Two-dimensional pseudo-homogeneous model is adopted with estimation of suitable parameters and its validity is corroborated by comparing simulation result with experimental data. The temperature of the molten salt and the feed composition are found to exercise significant influence on the yield of acrolein and the magnitude of hot spot. The temperature of the molten salt is usually kept constant. This study, however, suggests that the temperature of the molten salt must be axially adjusted so that the abrupt peak of hot spot should not appear near the reactor entrance. The yield of acrolein is maximized and the position and the magnitude of hot spot are optimized by the method of the iterative dynamic programming (IDP).

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$LiF-BeF_2$ 용융염계에서 전해제련에 의한 우라늄 회수 (Recovery of Uranium in $LiF-BeF_2$ Molten Salt System by Electrowinning)

  • 우문식;김응호;유재형
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.426-430
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    • 2003
  • 장수명핵종 소멸처리를 위한 건식분리공정에서 핵분열성물질인 우라늄을 장수명핵종과 분리할 필요가 있다. 본 실험은 $LiF-BeF_2$ 용융염에서 전해제련에 의한 우라늄 금속을 분리하기 위하여 분해전압 측정하였고, 인가전압에 따른 전해특성 파악 및 반응속도를 측정하였다. 측정결과 $500^{\circ}C$에서 $UF_4$$LiF-BeF_2$의 분해전압은 각각 -1.4volt와 -1.55volt이었다 우라늄의 전착속도는 우라늄 농도가 높을수록 증가하였다.

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MOLTEN SALT VAPORIZATION DURING ELECTROLYTIC REDUCTION

  • Hur, Jin-Mok;Jeong, Sang-Moon;Lee, Han-Soo
    • Nuclear Engineering and Technology
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    • 제42권1호
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    • pp.73-78
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    • 2010
  • The suppression of molten salt vaporization is one of the key technical issues in the electrolytic reduction process developed for recycling spent nuclear fuel from light-water reactors Since the Hertz-Langmuir relation previously applied to molten salt vaporization is valid only for vaporization into a vacuum, a diffusion model was derived to quantitatively assess the vaporization of LiCl, $Li_2O$ and Li from an electrolytic reducer operating under atmospheric pressure. Vaporization rates as a function of operation variables were calculated and shown to be in reasonable agreement with the experimental data obtained from thermogravimetry.